HL-1259, Special Rept 90-001:on 900730,fire-rated Assembly Declared Inoperable for More than 14 Days.Caused by Personnel Error. Hourly Fire Watch Initiated

Special Rept 90-001:on 900730,fire-rated Assembly Declared Inoperable for More than 14 Days.Caused by Personnel Error. Hourly Fire Watch Initiated

ML20059D587
Person / Time
Site:	Hatch
Issue date:	08/29/1990
From:	Hairston W GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-001, 90-1, HL-1259, NUDOCS 9009070111
Download: ML20059D587 (6)

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Geargia Power Campany

,.' 333 Piedmord Avenue o Atlanta. Georg:a 30308 1 pie @one 4D4 026 3195 +

WI.ng Adress l 40 inerress Center Parkway

- Post ONt Dax 1295 I B tmingham. Alabama 3L201 hphone 205 608 MB1 l'De 50t!!!Mwn t'ottt?C SVStr1D

) W. Q. Hairston, I!!

Semor Vice Prestdent '

Nuclear OperaSons HL-1259

, 000972

' August 29, 1990 f

P U.S. Nuclear Regulatory Commission ATTN: Document Control Desk-Washington, D.C. 20555 l PLANT HATCH - UNIT 1

-NRC DOCKET 50-321 OPERATING LICENSE DPR-57 SPECIAL REPORT 90-001 FIRE RATED ASSEMBLY INOPERABLE FOR LONGER 1

THAN 14 DAYS RESULTS IN SPECIAL REPORT AS REQUIRED BY FIRE HAZARDS ANALYSIS ,

Gentlemen:

In accordance with the requirements of the Unit 1 Technical Specifications and the Fire Hazards Analysis (FHA), Appendix B, Georgia Power Company is submitting the enclosed Special Report concerning an event where a fire rated assembly was inoperable for longer than 14 days. This event occurred at Plant Hatch Unit 1.

Sincerely, i 1 LO. -

W. G. Hairston, III JKB/eb j

Enclosure:

Fire-Rated Assembly Inoperable for. Longer than 14 Days Results in-Spe-ial Report as Required by Fire Hazards Analysis  !

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.. I GeorgiaJbwer Abk U.S. Nuclear Regulatory Comission August 29, 1990 i Page Two c: Gaornia Power Ca=nanv'  !'

l Mr. H. C. Nix, General Manager - Nuclear Plant Mr. J. D. Heidt, Manager Engineering and Licensing - Hatch  ;

NORMS U.S. Nuclear Reaulatory Comission. Washindon. D.C.  !

Mr. L. P. Crocker, Licensing Project M*aager - Hatch  !

t U.S. Nuclear Raoulatory Comission. Reaion II <

Mr. S. C. Ebneter, Regional M:!nistrator Senior Resident Inspector - Hatch ,

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. L ENCLOSURE PLANT HATCH - UNIT 1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 SPECIAL REPORT 90-001-FIRE RATED ASSEMBLY INOPERABLE'FOR-LONGER THAN 14 DAYS RESULTS IN SPECIAL REPORT i I

AS REQUIRED BY FIRE HAZARDS ANALYSIS l

A. REQUIREMENT FOR REPORT I This. report. is required by Unit 1 Technical -Specificatlons Sectiori-6.9.2. This- section of Technical Specifications states that special reports for fire protection equipment operating and surveillance -i requirmnts shall be submitted as required by the Fire Hazards Analysis (FW,) and its Appendix B requirements.

The FHA,1 Appendix B, Section 1.1.1, states that fire rated assemblies; separating portions:of redundant: systems important to safe shutdown j within a fire area shall be operable. ACTION statement b. of FHAs-

, Appendix B, Section-1.1.1, allows for the fire rated. assembly (s) to-be 1 inoperable for up to 14 days.- If this time is exceeded, a special-

-report is. required. The subject deficiency was. corrected within 14-days of identification. However, the deficiency remained unidentified for an undetermined period-of time, hence, this report is required.

B. UNIT STATUS AT TIME OF EVENT On 7/30/90, at approximately 0930 CDT, Unit I was in the.Run mode at an approximate power level of 2433 CMWT (approximately 100 percent of'

. ted thermal power). At that time it was determined that fire damper ,

F '-F003 was inoperable. ,

i C. DESCRIPTION OF EVENT

't On_7/30/90, at approximately 0930 CDT,- plant personnel were performing procedure 42SV FPX-006-05, " Fire Damper Surveillance" on fire damper ,

IT41-F003. The purpose of the procedure is to demonstrate-proper r.,peration of Heating Ventilation and Air Conditioning-(HVAC) Fire Dampers in Unit I and Unit.2. The procedure implements the requirements of h re Protection Equipment Operating and Surveillance-  ;

Requirements,-Appendix P,, Se,: tion 2.1.1.b of'tto' Fire Hazard Analysis.

The' procedure is performed once per 18 months. Fire damper.1T41-F003 is located in Fire Area i'll in UnitL1 Ret.ctor Building over the east door to the Recirculation Pump Motor-Gensrator Set Room "B" in penetration IT43-H038H.

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ENCLOSURE-(CONTINUED)-

SPECIAL REPORT 90-001 FIRE RATED ASSEMBLY INOPERABLE FOR LONGER THAN 14 DAYS RESULTS IN SPECIAL REPORT "

-AS-REQUIRED-BY FIRE' HAZARDS ~ ANALYSIS =

Per procedural step 7.2.4, a fire damper is o'perable when that dacper closes smoothly and seats securely in the end of the track. Ela:;t

-personnel found the subject. damper had been rotated:180 degrees. In

.this condition, the damper could-not hive moved to a closed position 9f

~ a fire had occurred. Thus, the damper was' declared inoperable.

Deficiency Card 1-90-5060 was written to: document the-condition as required by the plants administrative control procedgres. Limiting Condition for Operatiore (LCO) 1-90-440-was init(ated on 7/30/90,. at-- ) '

approximately 1050 CDT, and an hourly fire wate was established as

. required by FHA Appendix-8, Section 1.1.1, Action.a.

~ The damper.was einstalled in a' proper position on 7/30/90Lper Maintenance Work Order 1-90-5514, and demonstrated operable per surveillance procederc 12SV-FPX-006-OS. .LC0:1-90-440 was terminated on 7/31/90, at approximately-2050-CDT.

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O. CAUSE OF EVENT a

Fire damper IT41-F003 was rendered inoperable as a.resu'lt of personnel.

error i..ade by person (s)~ unknown., This damper was.previously. '

demonstrated operable,L as sp.vified by the acceptance criteriaL in procedure' 425V-FPX-006-OS, by a surveillance. performed on 4/17/89.

The subject damper became inoperable duri % the Unit 1 1990. spring outage as a result of outage work involving the: removal and replacement of the recirculation motor generator rotor. The damper was, ,

apparently, removed durir.g this activity .and inadvertently reinstalled  ;

incorrectly. ]

The results of surveillances performed on'the remaining;132IHVAC fire dampers in both' Units 1 and 2 confirmed the proper configuration of all o:...< HVAC dampers- It can be concluded that the' incorrect position of damper.IT41-F003 was an isolated event.

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ENCLOSURE (CONTINUED)

SPECIAL REPORT 90-001- ,

FIRE RATED ASSEMBLY INOPERABLE FOR LONGER j THAN 14 DAYS RESULTS IN SPECIAL REPORT 1 AS REQUIRED BY FIRE HAZARDS ANAL / SIS ]

E.. ANALYSIS OF EVENT In this event,-licensed personnel declared the deficient fire rated  ;

assembly inoperable on 7/30/90. = Appropriate fire detectors were j verified operable und an hourly fire watch was. established to comply, with ACTION statement a. of Section 1.1.1. ACTION statement a. requires

that: .)

With one or more of the required fire rated assemblies. I and/or sealing devices inoperable, within I hour establish-a continuous fire watch on at least one side of'the affected assembly (s) and/or 'sealinei device (s) or. verify the -!

operability of fire detectors on at least one side of the 1 inoperable assembly (s) and sealing device (s) and establish an hourly. fire watch patrol.

Also,' the affected fire area 1211 and adjacent fire area 1203K are equipped with smoke detectors. These detectors are tied-into the fire detection system which annunciates in the Main  !

Control Room in-the unlikely event'of a fire. . Additionally,1 a full coverage wet pipe suppression system'is provided for the- '

Motor-Generator Set Room B. . The system activates upon1 detection of a fire and results in an alarm both-locally andein ihe Main Control Room, s These actions and equipment aasured that if a fire had- 1 occurred, it would have been promptly detected and extinguished.

1 Based on the above inforation, it is conclud d that this event had no adverse impact on nut. lear safety.

F. CORRECTIVE ACTIONS

1. The affected fire dam

. hourly fire ~ watch was' per was diciared inoperable, and an initiated.

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ENCLOSURE (CONTINUED)-

SPECIAL REPORT 90-001 FIRE RATED ASSEMBLY INOPERABLE FOR LONGER- 1 I

THAN 14 DAYS RESULTS IN SPECIAL REPORT-

AS REQUIRED BY FIRE HAZARDS ANALY$1$'

2. The ' damper' was reinstalled ' in a proper position per; Maintenance Work Order 1-90-5514 and demonstrated operable l

-' per surveillance procedure 42SV-FPX-006-05.- LCO l-90-440 1 was' terminated on 7/31/90, at- approximately 2050 CDT.- l

3. An interdeoartmental ' memo has been issued by the plant  !!

General Ma' n ager stressing procedural requirements for the proper documentation and evaluation ~ of' activities ~ performed  :

in the plant, a

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